ANS / Publications / Journals / Nuclear Technology

Aging Tests of Neutron-Shielding Materials for Transport of Storage Casks

Herve Issard, Pascale Abadie

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 2-8

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems / dx.doi.org/10.13182/NT11-A12538

Accelerated Testing of Neutron-Absorbing Alloys for Nuclear Criticality Control

R. E. Mizia, T. E. Lister

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 9-21

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems / dx.doi.org/10.13182/NT11-A12539

Combined Experimental and Computational Approach to Predict the Glass-Water Reaction

E. M. Pierce, D. H. Bacon

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 22-39

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A12540

Feasibility of Reduced Boron Concentration Operation in Pressurized Water Reactor Plants

Aung Tharn Daing, Myung-Hyun Kim

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 40-56

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors / dx.doi.org/10.13182/NT176-40

Flashing-Induced Instability Analysis and the Start-Up of Natural Circulation Boiling Water Reactors

Rui Hu, Mujid S. Kazimi

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 57-71

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors / dx.doi.org/10.13182/NT11-A12542

Automatic Boiling Water Reactor Control Rod Pattern Design Using Ant Colony Optimization Algorithm

Cheng-Der Wang, Chaung Lin

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 72-82

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors / dx.doi.org/10.13182/NT11-A12543

Experimental Study on the Behavior of Suspended Aerosols of Sodium and Nonradioactive Fission Products (SrO₂ and CeO₂) in a Closed Vessel

V. Subramanian, R. Baskaran, J. Misra, R. Indira

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 83-92

Reactor Safety / dx.doi.org/10.13182/NT11-A12544

Analysis of the BR2 Loss-of-Flow Test A

Constantine P. Tzanos, B. Dionne

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 93-105

Thermal Hydraulics / dx.doi.org/10.13182/NT11-A12545

Using the Levenberg-Marquardt Method for Solutions of Inverse Transport Problems in One- and Two-Dimensional Geometries

Keith C. Bledsoe, Jeffrey A. Favorite, Tunc Aldemir

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 106-126

Radiation Transport and Protection / dx.doi.org/10.13182/NT176-106

High-Performance Differential Pressure Monitoring Devices Using Pulsating Sensors for a Sodium-Cooled Fast Breeder Reactor

K. Praveen, M. P. Rajiniganth, A. D. Arun, R. Ananthanarayanan, N. Malathi, P. Sahoo, N. Murali

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 127-137

Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT11-A12547

Yucca Mountain Waste Package Closure System Robotic Welding and Inspection System

C. I. Nichol, D. P. Pace, E. D. Larsen, T. R. McJunkin, D. E. Clark, M. L. Clark, K. L. Skinner, A. D. Watkins, H. B. Smartt

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 138-146

Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A12548

Hot-Test Results of the Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter for PWR Spent Fuel Rods

Tae-Hoon Lee, Young Soo Kim, Hee-Sung Shin, Ho-Dong Kim

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 147-154

Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT11-A12549

Review Paper: Review of Instrumentation for Irradiation Testing of Nuclear Fuels and Materials

Bong Goo Kim, Joy L. Rempe, Jean-François Villard, Steinar Solstad

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 155-187

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT11-A13294

Burnup Performance of Sodium-Cooled Fast Reactor by Utilizing Thorium-Based Fuels

Shadi Z. Ghrayeb, Kostadin N. Ivanov, Samuel H. Levine, Eric P. Loewen

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 188-194

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT11-A13295

Development of Effective Algorithm for Coupled Thermal-Hydraulic-Neutron-Kinetics Analysis of Reactivity Transient

Joanna Peltonen, Tomasz Kozlowski

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 195-210

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT11-A13296

Measurements of Aerosol Charge and Size Distribution for Graphite, Gold, Palladium, and Silver Nanoparticles

Matthew P. Simones, Veera R. Gutti, Ryan M. Meyer, Sudarshan K. Loyalka

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 211-226

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT10-10

Uranium Price Versus Cumulative Use

Clifford E. Singer, Hermann von Brevern

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 227-237

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT11-A13298

Computational Fluid Dynamics Analysis of Very High Temperature Gas-Cooled Reactor Cavity Cooling System

Angelo Frisani, Yassin A. Hassan, Victor M. Ugaz

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 238-259

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A13299

Assessment of MARS Code for Predicting Critical Heat Flux Under Heaving Conditions

Jin-Seok Hwang, Jong-Won Kim, Heon-Uk Nam, Goon-Cherl Park

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 260-273

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A13300

A C5 Benchmark Problem with the Discrete Ordinates Radiation Transport Code Denovo

G. Yesilyurt, K. T. Clarno, T. M. Evans, G. G. Davidson, P. B. Fox

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 274-283

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT11-A13301

Control Rod Drop Surveillance Using Two Friction Coefficients

J. Blázquez, I. Vallejo, A. García-Berrocal, M. Balbás

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 284-289

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT11-A13302

Separation of Transmutation- and Fission-Produced Radioisotopes from Irradiated Beryllium

Troy J. Tranter, Richard D. Tillotson, Nick R. Mann, Glen R. Longhurst

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 290-295

Technical Paper / Decontamination/ Decommissioning / dx.doi.org/10.13182/NT11-A13303

A Fruit of Yucca Mountain: The Remote Waste Package Closure System

Kevin Skinner, Greg Housley, Colleen Shelton-Davis

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 296-308

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT11-A13304

Measurement of Tritium During Voloxidation of Zircaloy-2 Cladding

Mark L. Crowder, James E. Laurinat, John A. Stillman

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Pages 309-313

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT11-A13305

Corrigendum

Nuclear Technology / Volume 176 / Number 2 / November 2011 / Page 314

dx.doi.org/10.13182/NT11-A13306

Neutronic Design and Analysis of a Small Nuclear Reactor to Supply District Heating and Electrical Energy to Canadian Forces Bases Located in the Arctic or the Northern Remote Communities

Stéphane Paquette, Hugues W. Bonin

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 315-336

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT11-A13311

Thermoeconomic Analysis of High-Temperature Gas-Cooled Reactors with Steam Methane Reforming for Hydrogen Production

Duk Jin Kim, Jong Hyun Kim, K. F. Barry, Ho-Young Kwak

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 337-351

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT11-A13312

Analyses of the Phébus FPT3 Experiment Using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE, and MELCOR

Georges Repetto, Olivier de Luze, Tilman Drath, Marco K. Koch, Thorsten Hollands, Klaus Trambauer, Christine Bals, Henrique Austregesilo, Jon Birchley

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 352-371

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT11-A13313

Triggered Steam Explosions with the Corium Melts of Various Compositions in a Two-Dimensional Interaction Vessel in the TROI Facility

J. H. Kim, B. T. Min, I. K. Park, S. W. Hong

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 372-386

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A13314

Neutron Channeling Through Neutron Absorber Sheets

Alan H. Wells, Albert J. Machiels

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 387-394

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT11-A13315

Use of Multiple Layers of Repeating Material to Effectively Collimate an Isotropic Neutron Source

Z. D. Whetstone, K. J. Kearfott

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 395-413

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT10-118

Advanced Cable-Testing Techniques for Nuclear Power Plants

Hashem M. Hashemian, Wendell C. Bean

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 414-429

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT11-A13317

Managing Beryllium in Nuclear Facility Applications

G. R. Longhurst, K. Tsuchiya, C. H. Dorn, S. L. Folkman, T. H. Fronk, M. Ishihara, H. Kawamura, T. N. Tranter, R. Rohe, M. Uchida, E. Vidal

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 430-441

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT11-A13318

Evolution of the Leak-Before-Break Concept in Nuclear Plants: Issues and Resolutions in the Process of Regulatory Actions

Mir Sajjad Ali

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 442-451

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT11-A13319

Laboratory Tests of an Ultrasonic Inspection Technique to Identify Defective CANDU Fuel Elements

W. H. Huang, T. W. Krause, B. J. Lewis

Nuclear Technology / Volume 176 / Number 3 / December 2011 / Pages 452-461

Technical Note / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT11-A13320